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All Journal Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega Jurnal Teknologi
Budiman, Arif Adtyas
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Civil Engineering, Building, Construction & Architecture Computer Science & IT Energy Engineering Materials Science & Nanotechnology

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Investigation of Heat Exchanger Performance in The Heating Tank Section of Loop FASSIP 03 NT Haryanto, Dedy; Budiman, Arif Adtyas; Putra, Muhammad Ganjar; Setiawan, Putut Hery; Juarsa, Mulya
Jurnal Teknologi Vol 16, No 1 (2024): Jurnal Teknologi
Publisher : Fakultas Teknik Universitas Muhammadiyah Jakarta

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.24853/jurtek.16.1.41-52

Abstract

The Passive System Simulation Facility (FASSIP) loop is an experimental test facility for a passive cooling system to recover the residual heat from decay produced by the reactor core during accident conditions. The Heating Tank Section (HTS) is one of the components of the FASSIP 03 NT facility. This component is equipped with a heat exchanger, 3 types of heat exchangers can be applied to HTS. Namely heat exchangers of the Straight Pipe Heat Exchanger (SPHE) type, the Straight Pipe Fins Heat Exchanger (SPFHE) type, and the Helical Pipe Heat Exchanger (HPHE) type. A modification was made to increase the efficiency of HTS, namely replacing the electric heater on the HTS from a ceramic band heater type to an immersion heater type. With this modification, it is necessary to know the performance of the heat exchanger on HTS and its speed in reaching operational temperature. The HPHE-type heat exchanger is more efficient than the SPHE-type and SPFHE-type heat exchangers. The HPHE-type heat exchanger has a much larger length of 5.5 m, so the thermal resistance (Rth) is very small, namely 0.003926 ℃/W. To reach the working fluid temperature in the range of 50 – 90 ℃, the HPHE-type heat exchanger requires 35 – 86 minutes.
Investigation of Natural Circulation Flow Under Steady-State Conditions Using a Rectangular Loop Roswandi, Iwan; Dimas, Dimas; Gunawan, Hyundianto Arif; Budiman, Arif Adtyas; Amelia, Almira Citra; Sanda, Sanda; Tjahjono, Hendro; Juarsa, Mulya
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 26, No 2 (2024): June 2024
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.55981/tdm.2024.7055

Abstract

Passive safety systems have garnered significant attention, particularly in situations where active systems fail. The comprehension of natural circulation phenomena plays a vital role in the advancement of passive cooling systems in nuclear power plants. The objective of this study is to examine the flow patterns under steady state conditions and assess the Grashof number. The experimental approach involved maintaining temperature differences of 60°C, 70°C, 80°C, and 90°C for a duration of 3 hours, with 3 replications. Alterations in temperature have an impact on the physical properties of water, such as density, viscosity, and specific heat. The calculations indicate that the minimum Grashof number occurs at 60°C (2.49×1012), while the maximum is observed at 90°C (9.42×1012), with an R2 value of 0.96533. Turbulent flow patterns were observed during each temperature fluctuation, which aligns with previous research on the Ress value of Grm/NG.
Co-Authors Amelia, Almira Citra Dedy Haryanto Dimas, Dimas Gunawan, Hyundianto Arif Hendro Tjahjono Mulya Juarsa Putra, Muhammad Ganjar Putut Hery Setiawan Roswandi, Iwan Sanda Sanda